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Proceedings Papers

Research on Heat Transfer Calculation of Ellipsoidal Melt Pool

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Peng Liu, Tao Zhou, Haolei Zhang, Xiaofang Liu
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A003, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134536
https://doi.org/10.1115/ICONE31-134536
View Paper titled, Research on Heat Transfer Calculation of Ellipsoidal Melt Pool
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Topics: Failure, Heat flux, Heat transfer, Pressure vessels, Metals, Wall thickness, Accidents, Heat, Pressurized water reactors, Ablation (Vaporization technology)
Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

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Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16897
https://doi.org/10.1115/ICONE2020-16897
View Paper titled, Probability of Rupture for WWER-1000 Main Piping
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Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations
Proceedings Papers

Experimental Study on Transient Heat Transfer for Helium Gas Flowing in a Minichannel

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Feng Xu, Qiusheng Liu, Satoshi Kawaguchi, Makoto Shibahara
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A039, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16697
https://doi.org/10.1115/ICONE2020-16697
View Paper titled, Experimental Study on Transient Heat Transfer for Helium Gas Flowing in a Minichannel
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Topics: Helium, Transient heat transfer, Heat, Flow (Dynamics), Temperature, Heat flux, Heat transfer coefficients, Transients (Dynamics), Control systems, Flowmeters
Proceedings Papers

Uranium Enrichment Measurement Using Enrichment-Meter Approach

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K. Abd El Gawad, Yushou Song
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A039, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82101
https://doi.org/10.1115/ICONE26-82101
View Paper titled, Uranium Enrichment Measurement Using Enrichment-Meter Approach
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Topics: Uranium, Containers, Simulation, Accuracy and precision, Wall thickness, Calibration, Dimensions, Equilibrium (Physics), Gamma ray spectrometry, Germanium
Proceedings Papers

Analytical Study of Supercritical Water Flow in Two Heated Parallel Channels With Wall Heat Effects

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Dhanashree S. Ghadge, Vijay Chatoorgoon
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A016, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81150
https://doi.org/10.1115/ICONE26-81150
View Paper titled, Analytical Study of Supercritical Water Flow in Two Heated Parallel Channels With Wall Heat Effects
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Topics: Flow (Dynamics), Heat, Water, Heat storage, Stability, Computer simulation, Wall thickness
Proceedings Papers

Study on Load Capacity of Main Steam Superpipe Nozzle Used in Nuclear Power Plant

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Zhou Gengyu, Liang Shuhua, Sun Lin, Lv Feng
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A075, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66965
https://doi.org/10.1115/ICONE25-66965
View Paper titled, Study on Load Capacity of Main Steam Superpipe Nozzle Used in Nuclear Power Plant
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Topics: Nozzles, Nuclear power stations, Steam, Stress, Pipes, Finite element analysis, Safety, Computational methods, Design, Extruding
Proceedings Papers

Boring Analysis in Solving Out-of-Tolerance of Wall Thickness of Surge Line in Nuclear Power Project

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Huadong Zhu
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A011, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66339
https://doi.org/10.1115/ICONE25-66339
View Paper titled, Boring Analysis in Solving Out-of-Tolerance of Wall Thickness of Surge Line in Nuclear Power Project
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Topics: Nuclear power, Surges, Wall thickness, Design, Pipes, Nuclear reactor coolants, Pressure, Engineering drawings, Fittings, Heating
Proceedings Papers

Application of Joint Boring Technique in Solving RCL Wall Thickness Problem

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Huadong Zhu
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A002, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66026
https://doi.org/10.1115/ICONE25-66026
View Paper titled, Application of Joint Boring Technique in Solving RCL Wall Thickness Problem
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Topics: Wall thickness, Design, In-service inspection, Inspection, Nuclear power, Nuclear power stations, Nuclear reactor coolants, Reactor vessels, Welded joints, Boilers
Proceedings Papers

Guided Waves As an Online Monitoring Technology for Long Term Operation in NPPs: New Experimental Results on a Steam Discharge Pipe

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Francesco Bertoncini, Mauro Cappelli, Francesco Cordella, Marco Raugi
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A038, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67444
https://doi.org/10.1115/ICONE25-67444
View Paper titled, Guided Waves As an Online Monitoring Technology for Long Term Operation in NPPs: New Experimental Results on a Steam Discharge Pipe
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Topics: Nuclear power stations, Pipes, Steam, Waves, Probes, Sensors, Testing, Circuits, Echoes, Engineering simulation
Proceedings Papers

The Research on Ultrasonic Testing Technology for Bottom Part of Reactor Pressure Vessel

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Ge Liang, Xu Xuguang, Cai Jiafan, Cheng Zhaoyu
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A027, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66984
https://doi.org/10.1115/ICONE25-66984
View Paper titled, The Research on Ultrasonic Testing Technology for Bottom Part of Reactor Pressure Vessel
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Topics: Reactor vessels, Ultrasonic testing, Probes, Inspection, Alloys, Nuclear power stations, Accuracy and precision, Circuits, Corrosion, Design
Proceedings Papers

In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR

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Zhou Lifeng, Cheng Zhaoyu, Cai Jiafan, Tang Yi
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A028, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66999
https://doi.org/10.1115/ICONE25-66999
View Paper titled, In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR
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Topics: In-service inspection, Pressurized water reactors, Fracture (Materials), Inspection, ASME Standards, Failure, Probes, Signals, Testing, Water
Proceedings Papers

Assessment of Choking Flow Models in RELAP5 for Subcooled Choking Flow Through a Small Axial Crack of a Steam Generator Tube

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Mark A. Brown, Hung Nguyen, Shripad T. Revankar, Jovica Riznic
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A046, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67371
https://doi.org/10.1115/ICONE25-67371
View Paper titled, Assessment of Choking Flow Models in RELAP5 for Subcooled Choking Flow Through a Small Axial Crack of a Steam Generator Tube
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Topics: Boilers, Flow (Dynamics), Fracture (Materials), Subcooling, Nuclear power stations, Coolants, Accidents, Hydraulics, Leakage, Leak-before-break
Proceedings Papers

Experimental Investigation of Subcooled Choking Flow in a Steam Generator Tube Crack

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Hung Nguyen, Mark Brown, Shripad T. Revankar, Jovica Riznic
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A017, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60309
https://doi.org/10.1115/ICONE24-60309
View Paper titled, Experimental Investigation of Subcooled Choking Flow in a Steam Generator Tube Crack
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Topics: Boilers, Flow (Dynamics), Fracture (Materials), Subcooling, Coolants, Design, Nuclear power stations, Pressurized water reactors, Rupture, Water
Proceedings Papers

Non-Invasive On-Line Monitoring for Nuclear Power Plants Using Guided Waves Propagating in Steel Pipes With Different Types of Structural Complexity

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Francesco Bertoncini, Mauro Cappelli, Francesco Cordella, Marco Raugi
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T01A010, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60885
https://doi.org/10.1115/ICONE24-60885
View Paper titled, Non-Invasive On-Line Monitoring for Nuclear Power Plants Using Guided Waves Propagating in Steel Pipes With Different Types of Structural Complexity
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Topics: Nuclear power stations, Pipes, Steel, Waves, Failure, In-service inspection, Inspection, Life extension, Radiation (Physics), Robustness
Proceedings Papers

Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression

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Chunzhen Yang, Jingquan Liu, Yuyun Zeng, Muhammad Saeed
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T01A012, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61114
https://doi.org/10.1115/ICONE24-61114
View Paper titled, Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression
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Topics: Support vector machines, Uncertainty, Modeling, Nuclear power stations, Algorithms, Carbon steel, In-service inspection, Maintenance, Pipes, Sampling methods
Proceedings Papers

Outline of Specification for Composite SC Walls in Nuclear Facilities

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Saahastaranshu R. Bhardwaj, Amit H. Varma, Taha Al-Shawaf
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T08A009, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60960
https://doi.org/10.1115/ICONE24-60960
View Paper titled, Outline of Specification for Composite SC Walls in Nuclear Facilities
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Topics: Composite materials, Nuclear power stations, Design, Shear (Mechanics), Steel, Failure, Safety, Accidents, Anchorage, Bending (Stress)
Proceedings Papers

Fretting Wear of the Zr Fuel Rod Cladding

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Ladislav Pecinka, Jaroslav Svoboda, Vladimír Zeman
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T03A027, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31103
https://doi.org/10.1115/ICONE22-31103
View Paper titled, Fretting Wear of the Zr Fuel Rod Cladding
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Topics: Cladding systems (Building), Fuel rods, Wear, Zirconium, Fuels, Nuclear power stations, Pressurized water reactors, Damage, Failure, Flow (Dynamics)
Proceedings Papers

A Study on Weld Residual Stress Relaxation by Local Post Weld Heat Treatment for Circumferential Weld

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Seung-gun Lee, Youngho Son
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T01A025, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31083
https://doi.org/10.1115/ICONE22-31083
View Paper titled, A Study on Weld Residual Stress Relaxation by Local Post Weld Heat Treatment for Circumferential Weld
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Topics: Heat treating (Metalworking), Relaxation (Physics), Stress, Finite element analysis, Heat, Alloy steel, Engineering standards, Fracture (Materials), Furnaces, Nuclear power stations
Proceedings Papers

The Role of CHECWORKS™ in an Effective FAC Program

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David Smith, Jeffrey Horowitz
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T01A016, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30854
https://doi.org/10.1115/ICONE22-30854
View Paper titled, The Role of CHECWORKS™ in an Effective FAC Program
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Topics: Accidents, Carbon steel, Computer software, Condensed matter, Corrosion, Engineers, Failure, Flow (Dynamics), Fossil fuels, Inspection
Proceedings Papers

Non-Linear Analysis of AP1000 Auxiliary and Shield Building Subjected to Combined Accident Thermal and Seismic Loadings

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J. Jennifer Zhang, Lee J. Tunon-Sanjur
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T03A030, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31263
https://doi.org/10.1115/ICONE22-31263
View Paper titled, Non-Linear Analysis of AP1000 Auxiliary and Shield Building Subjected to Combined Accident Thermal and Seismic Loadings
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Topics: Accidents, Concrete cracking, Finite element model, Reinforced concrete, Computer simulation, Concretes, Design, Fracture (Materials), Stiffness, Structural design